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in subjects: "Neutron Beams"  
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Creep Rupture in the Presence of a Fast Neutron Flux

Description: Possible mechanisms for creep rupture during irradiation are examined. Evidence that the rupture occurs by grain boundary sliding alone, or by vacancy condensation, is compared. It is observed that vacancy condensation is the more probable mechanism, and that this mechanism predicts a reduction in creep rupture life for metals exposed to a fast neutron flux (neglecting effects of radiation annealing). (T.F.H.)
Date: January 14, 1959
Creator: Gregory, D. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PRELIMINARY REPORT ON 2% U$sup 235$-ENRICHED UF$sub 4$-C$sub 25$H$sub 52$ CRITICAL ASSEMBLIES

Description: A series of critical experiments with blocks of 2% U/sup 235/--enriched UF/sub 4/-C/sub 25/sub 5/H/sub 52/ was initiated at the ORN L Critical Experiments Facility. Thus far assemblies with H:U/sup 235/ atomic ratios of 195 and 294 were built in parallelepipedal and simulated cylindrical geometries, both reflected and unreflected. From the results the minimum critical masses for reflected spheres were determined to be 16.3 and 8.5 kg of U/sup 235/ for fuel mixtures with H:U atomic ratios of 195… more
Date: April 22, 1959
Creator: Mihalczo, J T; Lynn, J J; Scott, D & Connolly, W C
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PROGRESS ON THE DEVELOPMENT OF URANIUM CARBIDE-TYPE FUELS

Description: It has been corfirmed that uranium monocarbide can be prepared by reacting uranium metal powder with methane at about 650 C, and that sintered carbides of greater than 90% of theoretical density can be made. The cast density of carbides has been found to vary from 13.56 g/cm/sup 3/ for UC to 11.7 g/cm/sup 3/ for UC/sub 2/. The electrical resistivity of cast carbides has been found to vary from about 40 microhm-cm for UC to about 90 microhm-cm for UC/sub 2/ . About 500 ppm of iron or silicon has… more
Date: August 21, 1959
Creator: Rough, F.A. & Chubb, W. eds.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ALUMINA-CLAD UO$sub 2$ FOR FUEL APPLICATIONS

Description: Using a special reactive form of high-purity alumina, claddings were applied to UO/sub 2/ particles by a tumbling technique. The clad pellets were isostatically pressed at 100,000 psi and then sintered at 2800 deg F in hydrogen. crack-free spheroidal pellets ranging from 1000 to 2000 mu in diameter were produced. The dense Al/sub 2/O/sub 3/ envelopes surrounding the UO/sub 2/ particles were estimated to be 300 to 500 mu thick. The Al/sub 2/O/sub 3/ claddings protected the UO/sub 2/ from oxidati… more
Date: February 18, 1959
Creator: Smalley, A.K.; Riley, W.C. & Duckworth, W.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

HIGH FLUX ISOTOPE REACTOR PRELIMINARY DESIGN STUDY

Description: A comparison of possible types of research reactors for the production of transplutonium elements and other isotopes indicates that a flux-trap reactor consisting of a beryllium-reflecteds light-water-cooled annular fuel region surrounding a light-water island provides the required thermal neutron fluxes at minimum cost. The preliminary desigu of such a reactor was carried out on the basis of a parametric study of the effect of dimensions of the island and fuel regions heat removal rates, and f… more
Date: March 20, 1959
Creator: Lane, J. A.; Cheverton, R. D.; Claiborne, G. C.; Cole, T. E.; Gambill, W. R.; Gill, J. P. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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